Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems

Applicability of SYSML and AADL

Joonas Linnosmaa, Janne Valkonen, Peter Karpati, André Hauge, Fabien Sechi, Bjørn Axel Gran

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

Complexity of modern control and safety systems challenge the usual linear document-based presentation of system design. This complicates the work of designers, assessors and regulators comprehending the system, whose understanding often depends on building a mental model of the system and thus assessing its suitability. More rigorous and structured way to represent the system, than the linear documents-based, is model-based approach. Based on a literature review, SysML and AADL were identified as suitable candidates. They were tried in an exploratory case study modelling APR1400 reactor protection system, based on its linear description from a real applicant’s design control document. Effort was also taken to extract safety assurance information (for independence) from the documentation and organize it into a structured safety argument. Research serves also to discuss the strengths and weaknesses of model-based specification and assessment compared to document-based approaches. Modelling of the system based on design document and extracting safety assurance information was challenging. Results, based on the modelling experiences and literature review, argue that the studied architecture languages offer benefits over the use of natural language in clarity, ambiguity and traceability. However, using these architecture description languages require extensive modelling expertise and effort to allow a smooth modelling process and understanding. In addition, multidisciplinary insight into the system at both the conceptual level as well as hardware and software level is required. We also identified support of classical safety analysis methods within SysML and AADL.
Original languageEnglish
Title of host publication11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
Subtitle of host publicationNPIC and HMIT 2019
PublisherAmerican Nuclear Society ANS
Pages276-289
ISBN (Electronic)978-0-8944-8783-5, 978-0-89448-758-3
Publication statusPublished - 2019
MoE publication typeA4 Article in a conference publication
Event11th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC&HMIT - Orlando, United States
Duration: 9 Feb 201914 Feb 2019
Conference number: 11

Conference

Conference11th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC&HMIT
Abbreviated titleNPIC&HMIT
CountryUnited States
CityOrlando
Period9/02/1914/02/19

Fingerprint

Specifications
Security systems
Systems analysis
Hardware
Control systems

Keywords

  • architecture description language
  • model-based systems engineering
  • safety critical systems
  • literature review

Cite this

Linnosmaa, J., Valkonen, J., Karpati, P., Hauge, A., Sechi, F., & Gran, B. A. (2019). Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems: Applicability of SYSML and AADL. In 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies: NPIC and HMIT 2019 (pp. 276-289). American Nuclear Society ANS.
Linnosmaa, Joonas ; Valkonen, Janne ; Karpati, Peter ; Hauge, André ; Sechi, Fabien ; Gran, Bjørn Axel. / Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems : Applicability of SYSML and AADL. 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies: NPIC and HMIT 2019. American Nuclear Society ANS, 2019. pp. 276-289
@inproceedings{923fd78c0dd44c4084cda7209da072aa,
title = "Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems: Applicability of SYSML and AADL",
abstract = "Complexity of modern control and safety systems challenge the usual linear document-based presentation of system design. This complicates the work of designers, assessors and regulators comprehending the system, whose understanding often depends on building a mental model of the system and thus assessing its suitability. More rigorous and structured way to represent the system, than the linear documents-based, is model-based approach. Based on a literature review, SysML and AADL were identified as suitable candidates. They were tried in an exploratory case study modelling APR1400 reactor protection system, based on its linear description from a real applicant’s design control document. Effort was also taken to extract safety assurance information (for independence) from the documentation and organize it into a structured safety argument. Research serves also to discuss the strengths and weaknesses of model-based specification and assessment compared to document-based approaches. Modelling of the system based on design document and extracting safety assurance information was challenging. Results, based on the modelling experiences and literature review, argue that the studied architecture languages offer benefits over the use of natural language in clarity, ambiguity and traceability. However, using these architecture description languages require extensive modelling expertise and effort to allow a smooth modelling process and understanding. In addition, multidisciplinary insight into the system at both the conceptual level as well as hardware and software level is required. We also identified support of classical safety analysis methods within SysML and AADL.",
keywords = "architecture description language, model-based systems engineering, safety critical systems, literature review",
author = "Joonas Linnosmaa and Janne Valkonen and Peter Karpati and Andr{\'e} Hauge and Fabien Sechi and Gran, {Bj{\o}rn Axel}",
note = "{"}The American Nuclear Society gives you permission to publish your final paper from the NPIC&HMIT 2019 meeting on your company’s publication data base. Please do not publish this paper on your data base until the proceedings is published in May. Ellen Leitschuh 708-579-8253{"}",
year = "2019",
language = "English",
pages = "276--289",
booktitle = "11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies",
publisher = "American Nuclear Society ANS",
address = "United States",

}

Linnosmaa, J, Valkonen, J, Karpati, P, Hauge, A, Sechi, F & Gran, BA 2019, Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems: Applicability of SYSML and AADL. in 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies: NPIC and HMIT 2019. American Nuclear Society ANS, pp. 276-289, 11th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC&HMIT , Orlando, United States, 9/02/19.

Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems : Applicability of SYSML and AADL. / Linnosmaa, Joonas; Valkonen, Janne; Karpati, Peter; Hauge, André; Sechi, Fabien; Gran, Bjørn Axel.

11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies: NPIC and HMIT 2019. American Nuclear Society ANS, 2019. p. 276-289.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

TY - GEN

T1 - Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems

T2 - Applicability of SYSML and AADL

AU - Linnosmaa, Joonas

AU - Valkonen, Janne

AU - Karpati, Peter

AU - Hauge, André

AU - Sechi, Fabien

AU - Gran, Bjørn Axel

N1 - "The American Nuclear Society gives you permission to publish your final paper from the NPIC&HMIT 2019 meeting on your company’s publication data base. Please do not publish this paper on your data base until the proceedings is published in May. Ellen Leitschuh 708-579-8253"

PY - 2019

Y1 - 2019

N2 - Complexity of modern control and safety systems challenge the usual linear document-based presentation of system design. This complicates the work of designers, assessors and regulators comprehending the system, whose understanding often depends on building a mental model of the system and thus assessing its suitability. More rigorous and structured way to represent the system, than the linear documents-based, is model-based approach. Based on a literature review, SysML and AADL were identified as suitable candidates. They were tried in an exploratory case study modelling APR1400 reactor protection system, based on its linear description from a real applicant’s design control document. Effort was also taken to extract safety assurance information (for independence) from the documentation and organize it into a structured safety argument. Research serves also to discuss the strengths and weaknesses of model-based specification and assessment compared to document-based approaches. Modelling of the system based on design document and extracting safety assurance information was challenging. Results, based on the modelling experiences and literature review, argue that the studied architecture languages offer benefits over the use of natural language in clarity, ambiguity and traceability. However, using these architecture description languages require extensive modelling expertise and effort to allow a smooth modelling process and understanding. In addition, multidisciplinary insight into the system at both the conceptual level as well as hardware and software level is required. We also identified support of classical safety analysis methods within SysML and AADL.

AB - Complexity of modern control and safety systems challenge the usual linear document-based presentation of system design. This complicates the work of designers, assessors and regulators comprehending the system, whose understanding often depends on building a mental model of the system and thus assessing its suitability. More rigorous and structured way to represent the system, than the linear documents-based, is model-based approach. Based on a literature review, SysML and AADL were identified as suitable candidates. They were tried in an exploratory case study modelling APR1400 reactor protection system, based on its linear description from a real applicant’s design control document. Effort was also taken to extract safety assurance information (for independence) from the documentation and organize it into a structured safety argument. Research serves also to discuss the strengths and weaknesses of model-based specification and assessment compared to document-based approaches. Modelling of the system based on design document and extracting safety assurance information was challenging. Results, based on the modelling experiences and literature review, argue that the studied architecture languages offer benefits over the use of natural language in clarity, ambiguity and traceability. However, using these architecture description languages require extensive modelling expertise and effort to allow a smooth modelling process and understanding. In addition, multidisciplinary insight into the system at both the conceptual level as well as hardware and software level is required. We also identified support of classical safety analysis methods within SysML and AADL.

KW - architecture description language

KW - model-based systems engineering

KW - safety critical systems

KW - literature review

UR - http://www.scopus.com/inward/record.url?scp=85071027139&partnerID=8YFLogxK

M3 - Conference article in proceedings

SP - 276

EP - 289

BT - 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies

PB - American Nuclear Society ANS

ER -

Linnosmaa J, Valkonen J, Karpati P, Hauge A, Sechi F, Gran BA. Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems: Applicability of SYSML and AADL. In 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies: NPIC and HMIT 2019. American Nuclear Society ANS. 2019. p. 276-289